Home > Publications database > Theoretische Untersuchungen zur Neutronenphysik des Blankets von D-T Fusionsreaktoren |
Book/Report | FZJ-2017-07341 |
1973
Kernforschungsanlage Jülich, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/15794
Report No.: Juel-0931-RG
Abstract: This study gives a report an neutronic calculations which have been performed to design the blanket of a D-T fusion reactor. First the paper presents an introduction to the operation conditions and the size of a fusion reactor . Since the fuel tritium is not found in nature it must be breeded in the blanket of the reactor. The transport theory has to be applied for the calculations of the neutron economy in a fusion reactor blanket. For that purpose, the numerical method of discrete ordinates and the Monte Carlo method are discussed as they are used in the calculations. Various blanket assemblies with different material compositions are studied with regard to their tritium generation potential, considering new measurements of the (n,2n) cross section of niobium. The importance of this cross section for fusion reactortechnology is discussed. The application of beryllium for neutron multiplication is also investigated. Some possible materials of both vacuum wall and structure are compared neutronically.
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